The NOSTRA code verification with using transients initiated by VVER control rod movement
- 1. Russian Research Centre Kurchatov Inst., Moscow (Russian Federation). Inst. of Nuclear Reactors
- 2. Moscow State Engineering Physics Inst. (Russian Federation)
Description
The comparison is presented of the data on transients obtained in the critical test facility of RRC Kurchatov Institute and during the startup of VVER-1000 power units with the results of NOSTRA dynamical calculations. For the critical test facility and power units were the experiments carried out with the movement of an individual control rod, a group of control rods and scram rods. The results for experimental values of reactivity are compared with the dynamical calculations and calculations using the quasicritical methods. A good agreement between the results obtained in the calculations and in experiments is found, which demonstrates the possibility of using the NOSTRA code for calculations of transients in the VVER-1000 operation. (author)
Additional details
Publishing Information
- Publisher
- Magyar Tudomanyos Akademia, KFKI Atomenergia Kutato Intezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 963-372-615-8
- Imprint Title
- Proceedings of the eighth Symposium of AER
- Imprint Pagination
- 766 p.
- Journal Page Range
- p. 297-311
Conference
- Title
- 8. Symposium of VVER reactor physics and reactor safety
- Dates
- 21-25 Sep 1998
- Place
- Bystrice nad Perstejnem (Czech Republic)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Hungary
- INIS RN
- 31028931
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; CONTROL ELEMENTS; CRITICAL SIZE; FUEL ASSEMBLIES; KALININ-3 REACTOR; N CODES; REACTOR START-UP; ROD DROP METHOD; SCRAM RODS; TEST FACILITIES; TRANSIENTS; WWER-5 REACTOR
- Descriptors DEC
- COMPUTER CODES; CONTROL ELEMENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIZE; START-UP; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 1 ref.